ML20091F034
| ML20091F034 | |
| Person / Time | |
|---|---|
| Site: | Vogtle  |
| Issue date: | 11/01/1991 |
| From: | Matthews D Office of Nuclear Reactor Regulation |
| To: | Georgia Power Co, Oglethorpe Power Corp, Municipal Electric Authority of Georgia, City of Dalton, GA |
| Shared Package | |
| ML20091F038 | List: |
| References | |
| NPF-68-A-048 NUDOCS 9111220233 | |
| Download: ML20091F034 (18) | |
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g[n UNITED STATES
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2o i NUCLEAR REGULATORY-COMMISSION WASHINoToN. D.C, 20666 o%,,. /
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GEORGIA POWER COMPANY OGLETHORPE POWER CORPORATION
.I MUNICIPAL ELECTRIC AUTHORITY OF GEOPGIA CITY OF 0 ALTON, GEORGIA
-V0GTLE ELECTRIC GENERATING PLANT, UNIT 1 AMEH0HENT TO FACILITY OPERATING LICENSE Amendment No. 48 License No. NPF-68 1.-
The Nuclear Regulatory Commission (the Comission) has found that:
A.
The application for amendment to the Vogtle Electric Generating Plant, Unit 1 (the f acility), Facility Operating License No.. NPF-68 filed by the Georgia Power company, acting for itself, Oglethorpe Power Corporation, Municipal Electric-Authority of Georgia, and City.
of Dalton, Georgia'(the licensees), dated August la, 1990, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act),.and the Comission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Corrission; C.
There is reasonable assurance'(i) that the activities authorized by
.this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be
-conducted in compliance with the Comission's regulations set forth
'in 10 CFR Chapter I; D.
The issuance of this license coendment will not.be inimical to:the comon defense and security or to the health and safety of the public; and
'E.
The issuance of this amendment is in accordance with 10 CFR'Part 51 of the Comission's regulations and all applicable requirements have
-been satisfied.
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9111220233 931102 PDR. ADOCK 05000424
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. 2.
Accordingly, the license is hereby amended by page changes to the Technical Specifications as indicated in the attachment to this license amendment and paragraph 2.C.(2) of facility Operating License No. NPF-68 is hereby amended to read as follows:
Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 48, and the Environmental Protection Plan contained in Appendix B, both of which are attached hereto, are hereby incorporated into this license. GPC shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
3.
This license amendment is effective beginning with the initial loading of VANTAGE-5 fuel into Unit 1 Cycle 4 FOR THE NUCLEAR REGULATORY COMMISSION
$3A N b!(.
r > t9-David B. Matthews, Prcject iirector Project Directorate 11-3 Division of Reactor Projects - 1/11 Office of Nuclear Reactor Regulation
Attachment:
Technical Specification Changes Date of issuance: November 1, 1991 e
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$I UNITED STATES e
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>i NUCLEAR REGULATORY COMMISSION 3
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% *.ha GEORGIA POWER COMPANY-OGLETHORPE POWFR CORPORATION HUNICIPAL ELECTRIC Alnt'ORITY OF GEORGIA CITY OF DALTON, GEORGIA V0GTLE ELECTRIC GENERATING PLANT, UNIT 2 EtENDMENT-TO FAClllTY OPERATING LICENSE Amendment No. 27 License No, NPF-81 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment to the Vogtle Electric Generating Plant, Unit 1 (the facility), Facility Operatirg License No. NPF-81 filed by the Georgia Power Company, acting for itself, Oglethorpe Power Corporation, Municipal Electric Authority of Georgia.-and City of Dalton, Georgia (the licensees), dated August 14, 1990, complies with the standards and requirenents of the Atomic Energy Act of 1954, as amended (the Act), and the Comission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Comission; C.
There is reasonable assurance (i) that the activities authorized by this amendr.ert can be conducted without endangering The health and safety of the public, and (ii) that such activities will be conducted in compliance with the Comission's regulations set forth
-in 10 CFR-Chapter I;
-D.
The issuance of this license amendment will not be inimical to the-comon defense and-security or tc the health and safety of the public; and E.
The issuance of this amendr:ent is in accordance with 10 G*h Part 51 of the Comission's regulations and all applicable requirenents have been satisfied.-
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2.
Accordingly, the license is hereby amended by page changes to the Technical Specifications as indicated in the attachment to this license amendment and paragraph 2.C.(2) of Facility Operating License No. NPI-B1 is hereby amended to read as follows:
Technical Specifications and Ervironmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 27, and the Environmental Protection Plan contained in Appendix B, both of which are attached hereto, are hereby incorporated into this license. GPC sttill operate it.e f acility in accordance with t5e Technical Specifications anc the Environmental Protection Plan.
3.
This license amendment is effective beginning with the initial loading of VANTAGE-5 fuel into Vogtle Unit 1 Cycle 4 FOR THE NUCLEAR REGULATORY COMMISSION an/R kl(;
IQ s W Davi B. Hat hews, Project Director Project Directorate 11-3 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Attachment:
Technical Specification Changes Date of issuance: November 1,1991 L
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UNITED STATES i
NUCLEAR flEGULATORY COMMISSION 3t -
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WASHINGTON, D.C. 20%6
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GEORGIA POWER COMPANY l
OGLETHORPE POWER COPP0 RATION MUNICIPAL ELECTRIC AUTHORITY Q GEORGIA CITY OF DALTON, GEORGIA V0GTLE ELECTRIC GENERATING PLANT, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 49 License No. HPF-68 1.
The Nuclear Regulatory Comission (the Commission) has found that:
A.
The application for anencrert to the Vogtle Electric Generating Plant Unit 1 (the facility), Facility Operating License No. NPF-68 filed by the Georgia Power Company, acting for itself, Oglethorpe Power Corporation, Municipal Electric Authority of Georgia, and City of Dalton, Georgia (the licensees), dated August 14, 1990, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of toe Comission; C.
There is reasonable assurance (1) that the activities authorized by this amendment can be conducted withot*t endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance w'th the Comission's regulations set forth in 10 CFR Chapter I; D.
The issuance of this license amendment will not be inimical to the comon defense and security er to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable requirements have been satisfied.
. 2.
Accordingly, the license is hereby amended by page changes to the Technical Specifications as indicated in the attachment to this license amendment and paragraph 2.C.(?) of Facility Operating License No. NPF-68 is herei,y amended to read as fol'cws:
Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Anendnent No. 49, and the Environmental Protection Plan contained in Appendix B, both of which are attached beerte, are hereby incorporated into this license. GPC shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
3.
_This license amendment is effective beginning with the initial loading of VANTAGE-5 fuel into Vogtle Unit 2 Cycle 3.
FOR THE NUCLEAR RECULATORY COMMISSION C9L C
WW David B. Matthews, Project Director Project Directorate 11-3 Division of Reactor Projects - 1/11 Office of Nuclear Reactor Regulation
Attachment:
Technical Specification Changes Date of. Issuance: November 1, 1991
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o UNIT E D STATES
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NUCLEAR REGULATORY COMMISSION 3 v.y i
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GEOR^ilA F0WER COMPANY OGLETHORPE POWER CORR 0 RAT 10H MllNICIPAL EtECTRIC AtlTHORITY Of GEOPGIA CITY OF DAt.T6N, CE0 Ail A V0GYLE ELECTkiC GENERATING PLANT,llNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendme No. 28 License
,, NPF-81 1.
The Nuclear Regulatory Comission (the Commission) has found that:
A.
The application for amendment to the Vogtle Electric Generating Plant Unit 1 (the facility), Facility Operating License No. NPF-81 filed by the Georgia Power Company, acting for itself, Oglethorpe Power Corporation, Municipal Electric Authority of Georgia, and City of Dalton, Georg16 (the licensees), dated August 14, 1990, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.
There is reasonable assurance (1) that the activities authorized 'j this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Comission's regulations set forth in 10 CFR Chapter I; D.
The issuance of this license amendment will not be inimical to the conuson defense and security or to the health and safety of the public; and E.
The issu :e of this anendment is in eccordance with 10 CFR Part 51 of the smmission's regulations an.,all applicable requirements have been su O fied.
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2.
Accordingly, the license is hereby amended by page changes to the Ter.hnical Specifications as indicated in the attachment to this license amendment and paragraph 2.C.(2) of facility Operating License No. NPF-81 is hereby amended to read as follows:
Technical Specifications,and Environnental Protec+ ion Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 28, and the Environmental Protection Plan contained in Appendix B, both of which are attached hereto, are hereby incorporated into this license. GPC shall operate the facility in accordance with the Technical specifications and the Environmental Protection Plan.
3.
This license amendment is effective beginning with the initial loading of VANTAGE 5 fuel into Vogtle Unit ? Cycle 3.
FM THE NUCLEAR REGULATORY C0kNibs10N ZID01}&,kfnste[v David B. Matthews, Project Dir ctor Project Directorate 11-3 Division of Reactor Projects - 1/11 Office of Nuclear Reactor Regulation
Attachment:
Technical Specification Changet Date of Issuance: November 1, 1991 e
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ATTACRMENT TO LICENSE AMENDHENT No$. 48 AND 44 FACILITY OPERATING LICENSE NO. NPr f>8 AND LICENSE AMENDPENTS NOS. 27 AND 28 FACILITY OPERATING tlCFNSE NO. NPF-81 DOCKETS NOS. 50-4?4 AND 50-475 Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages. The revised pages are identified by Arendment numbers and contain vertical lines indicating the areas of change.
Remove Pages insert Pages PHASE 1 (Effective beginning with the initial loading of VANTAGE-5 fuel into Vogtle Unit 1 Cycle 4) 2-4 2-4 2-12 2-1?
8 2-4 B ?-4
-3/4 3-1* and 3/4 3-?
3/4 3-1* and 3/4 3-2 3/4 3-9 and 3/4 3-10*
3/4 3-9 and 3/4 3-10*
PHASE 2 (Effective beginning with the initial loading of VANTAGE-5 fuel into Yogtle Unit ? Cycle 3. INSERT THESE PAGES AFTER 1HSERTING AMENDMENT NOS. 44 AND 46 (Unit 1), 24 AND 25 (Unit ?))
2-4 2-4 3/4 3-9 and 3/a 3-10*
3/4 3-9 and 3/4 3-10*
' Overleaf pages without changes (not enclosed)
NLtSE 1 Effective beginning with Unit 1 Cycle 4 f 't-o
THIS PAGE AFPLICABLE TO UNIT 1 ONLY TABLE 2.2 UNIT 1 r"
REACTOR TRIP SYSTEM INSTRUMEMTATION TRIP SETPOINTS E:q TOTAL SENSOR vg,'
ALLOWANCE ERROR FUNCTIONAL UNIT (TA)
Z
_(S)
TRIP SETPOINT ALLOWABLE VALUE
[
1.
Manual Reactor Teip N.A.
N.A.
N.A.
N.A.
N.A.
2.
Power Range, Neutron Flux (NI-0041B&C, NI-0042B&C, NI-0043B&C, NI-0044B&C) a.
High Setpoint 7.5 4.56 0
<1P9Y of RTP#
<111.3% of RTP#
b.
Low Setpoint 8.3 1.56 0
{25%ofRTP#
327.3%ofRTP#
3.
Power Range, Neutron Flux,
- 1. 6 0.50 0
<S% of RTP# with
<6.3% of RTP# with High Positive Rate a time constant a time constant (NI-0041B&C, NI-0042B&C, q)
NI-0043B&C, NI-0044B&C)
->2 seconds
>2 seconds 4.
DELETED 5.
Intermediate Range, 17.0 8.41 0
-<25% of RTP#
<31.E% of RTP#
Neutron Flux (NI-00358, NI-00368) 6.
Source Range, Neutron Flux 17.0 10.01 0
<105 2 >>
(NI-00318,NI-00328) cps
-<1.4 x 105 cps 55 EL El 7.
Overtemperature AT 10.7 7.04 1.96 See Note 1 See Note 2 38 (TDI-411C, TDI-421C, (UNIT 1)
(UNIT 1) + 1.17 EL E!
TDI-431C, TDI-441C)
,(UNIT 1)
EIEI 8.
Overpower AT 4.3 1.54 1.96 See Note 3 See Note 4 ko k.
(TDI-4118, TDI-4218, (UNIT 1)
(UNIT 1)
TDI-4318, TDI-4418)
E2 y%
- RTP = RATED THERMAL POWER St L
l THIS PAGE APPLICABLE TO UNIT 2 ONLY lABLE 2.2-la - UNIT 2 S
E REACTOR TRIP SYSTEM INSTRUMENTATION TRIP SETPOINTS C3 TOTAL SENSOR N
ALLOWANCE ERROR FUNCTIONAL UNIT (TA)
Z 15)
TRIP SETPOINT ALLOWABLE VALUE w
e 1.
Manual Reactor Trip N.A.
N.A.
N.A.
N.A.
N.A.
2.
Power Range, Neutron Flux (NI-0041B&C, NI-0042B&C, NI-0043B&C, NI-0044B&C) a.
High Setpoint 7.5 4.56 0
<109% of RTP#
<111.3% of RTP#
b.
Low Setpoint 8.3 4.56 0
{25%ofRTP#
??7.3%ofRTP#
Power Range, Neutron Flux, 1.6 0.50 0
(5% of RTP# with
<6.3% of RTF# with a.
i time constant i time constant High Positive Rate (NI-0041B&C, NI-0042B&C,
~>2 seconds
~>2 seconds NI-0043BSC, NI-0044B&C) l 4.
Deleted S.
Intermediate Range, 17.0 8.41 0
$25% of RTP#
$31.1% of RTP#
Neutron Flux (NI-0035B, NI-0036B) 5 6.
Source Range, Neutron Flux 17.0 10.01 0
-<105
<1.4 x 10 cps cps yp (NI-0031B,NI-0032B) 6.
EE 7.
Overtemperature AT 6.6 3.37 1.95 See Note 1 See Note 2 25 (TDI-411C,TDI-421C, (UNIT 2)
(UNIT 2) + 0.50 EE TDI-431C, TDI-441C)
(UNIT 2)
EE 8.
Overpower AT 4.9 1.54 1.95 See Note 3 See Note 4 Lb (TDI-411B,TDI-4218, (UNIT 2)
(UNIT 2) l TDI-4318,TDI-441B) 1 EE
- RTP = RATED THERMAL POWER 33
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vu
LlHITING SAFETY SSTEM SET
- M BASES REACTOR TRIP SYSifM INSTNMENTATION SETP0lWTS (Continued)
The various Reactor trip circuits automatically open the Reactor trip breakers whenever a condition monitored by the Reactor Trip System reaches a preset or calculated level.
In addition to reduadant channels and trains, the design approach provides a Reactor Trip System which monitors numerous system variables, therefore providing Trip System functional diversity.
The functional capatiility at the specified trip setting is required for those anti:1patory or diverse rieactor trips for which no direct credit was assumed in the safety analysis to enhance tm overall reliability of the Reactor Trip System.
The Reactor Trip System initiate a Turbine trip signal whenever Reactor trip is in'i.f ated.
This prevents the reactivity insertion that would otherwise result from excessive Reactor Coolant System cooldown and thus avoias unnecessary actuation of the Engineered Safety Features Actuation System.
M_anual Reactor Trip The Reactor Trip System includes manual Reactor trip capability.
Power Range, Neutron Flux In each of the Power Range Neutron flux channels there are two independent bistables, each with its own trip setting used for a High and Low Range trip setting.
The Low Setpoint trip provides protection during subcritical and low power operations to mitigate the consequences of a power excursion beginning from low power, and the High Setpoint trip provides protection during power operations to mitigate the consequences of a reactivity excursion from all power levels.
The Low Setooint trip may be manually blocked above P-10 (a power level of approximately 10% of RATED THERMAL POWER) and is automatically reinstated below the P-10 Setpoint.
Power Range, Neutron Flux, High Rates P
The Power Range Positive Rate trip provides protection against rapid flux increases which are characteristic o' a rupture of a control rod drive housing.
Specifically, this trip complements the Power Range Neutron Flux High and Low trips to ensure that the criteria are met for rod ejection from mid-power.
V0GTLE UNITS - 1 & 2 B 2-4 Amendment No. 48 (Unit 1)
Amendment No. 27 (Unit 2)
TABLE 3.3-1
<8p REACTOR TRIP SYSTEM INSTRUMENTATION m
g MINIMUM
=
TOTAL NO.
CHANNELS CHANNELS APPLICABLE v.
FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERABLE MODES ACTION
[
1.
1 2
1, 2 1
a a
N 2
1 2
3, 4, 5' 11 2.
Power Range, Neutron Flux (NI-0041B&C, NI-0042B&C, NI-00438&C,NI-00448&C)
D a.
High Setpoint 4
2 3
1, 2 2
d b
b.
Low Setpoint 4
2 3
I,2 2
D 3.
Power Range, Neutron Flux, 4
2 3
1, 2 S
mg High Positive Rate (NI-0041S&C, NI-0042B&C, w
NI-0043B&C, NI-0044B&C) m 4.
(Deleted) 5.
Intermediate Range, Neutron Flux
$5 (NI-0035B,D&E yy NI-0036B,D&G) d E$
a.
Power Operation 2
1 2
I 3
((
b.
Startup 2
1 2
2 3
OO 6.
Source Range, Neutron Flux
]
(NI-0031B,D&E,NI-0032B,0&G)
EE a.
Startup 2
1 2
25 4
33 b.
Shutdown 2
1 2
3, 4, 5 5
3 00
TABLE 4.3-1 REACTOR TRIP SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS 6
TRIP S
ANALOG ACTUATING MODES FOR E
CHANNEL DEVICE WHICH c
CHANNEL CHANNEL OPERATIONAL OPERATIONAL ACTUATION SURVEILLANCE
- i FUNCTIONAL UNIT CHECK CALIBRATION TEST TEST LOGIC TEST IS REQUIRED M
1.
Manual Reactor Trip N.A.
N.A.
N.A.
R(14)
N.A.
1 2, 3, 4,
8 a
3 w
S e.
2.
Power Range,' Neutron Flux (NI-0041B&C,NI-0042B&C, m
NI"0043B&C,NI-00448&C) i 1
l a.
High Setpoint S
O(2, 4),
Q(17)
N.A.
N.A.
1, 2 i
M(3,4),
Q(4, 6),
R(4,5) d b.
Low Setpoint S
R(4)
S/U(1)
N.A.
N.A.
I,2 3.
Power Range, Neutron Flux, N.A.
R(4)
Q(17)
N.A.
N.A.
1, 2 w2 High Positive Rate (NI-0041B&C, NI-0042B&C, wa NI-0043B&C, NI-00448&C) 4.
(Deleted) d 5.
Intermediate Range, S
R(4, 5)
S/U(1)
N.A.
N.A.
I,2 Neutron Flux FF (NI-00358,0&E,
@g NI-00368,0&G)
C 23 6.
Source Range, Neutron Flux 5
R(4,5)
S/U(1),Q(9,17)
N.A.
N.A.
2, 3, 4, 5 (NI-0031B,D&E, y,F NI-0032B,D&G)
N$
7.
Overtemperature AT S
R(12)
Q(17)
N.A.
N.A.
1, 2 1
(TDI-0411C, TDI-0421C, g&
TDI-0431C, TDI-0441C) t-l 4
t-m
e I
J PilASE 2 Effective leginning with Unit 2 Cycle 3 1
i t
l l
TABLE 2.2-1 h
REACTOR TRIP SYSTEM INSTRUMENTATION TRIP SETPOINTS m
TOTAL SENSOR E
ALLOWANCE ERROR FUNCTIONAL UNIT (TA)
Z (S)
TRIP SETPOINT ALLOWABLE VALUE g
J.,
1.
Manual Reactor Trip N.A.
N.A.
N.A.
N.A.
N.A.
2.
Power Range, Neutron Flux (NI-0041B&C, NI-0042B&C, N
NI-0043B&C, NI-0044B&C) a.
High Setpoint
- 7. 5 4.56 0
<109% of RTC#
<111.3% of RTP#
b.
Low Setpoint 8.3 4.56 0
325%ofRTP#
[27.1 of RTP#
3.
Power Range, Neutron Flux, 1.6 0.50 0
<5% of RTP# with
<6.3% of RTP# with High Positive Rate i time constant a time constant (NI-0041B&C, NI-0042B&C, NI-0043B&C,NI-0044B&C)
->2 seconds
~>2 seconds 1
4.
DELETED m
E 5.
Intermediate Range, 17.0 8.41 0
<25% of RTP#
<31.1% of RTP#
Neutron Flux (NI-0035B, NI-00368) 6.
Source Range, Neutron Flux 17.0 10.01 0
<105 cps
~<1.4 x 105 (NI-00318, NI-00328) cps pp 7.
Overtemperature aT 10.7 7.04 1.96 See Note 1 See Note 2 (TDI-411C, TDI-421C,
+ 1.17 mm hh TDI-431C, TDI-441C)
E$
8.
Overpcwer AT 4.3 1.54 1.96 See Note 3 See Note 4 (TDI-4118,TDI-4218, ff TDI-4318, TDI-4418) se
- RTP = RATED THERMAL POWER CC dd r,+
Noa sw
TABLE 4.3-1 REACTOR TRIP SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS 8
TRIP El ANALOG ACTUATING MODES FOR E
CHANNEL DEVICE WHICH c
CHANNEL CHANNEL OPERATIONAL OPERATIONAL ACTUATION SURVEILLANCE
- " FUNCTIONAL UNIT
, CHECK CALIBRATION TEST' TEST LOGIC TEST IS REQUIRED w
a a
1.
Manual Reactor Trip N.A.
N.A.
N.A.
R(14)
N.A.
1 2, 3, g,
3 5
o-2.
Power Range, Neutron Flux (NI-0041B&C,NI-0042B&C, m
NI-0043B&C,NI-0044B&C) a.
High Setpoint 5
0(2,4),
Q(17)
N.A.
N.A.
1, 2 M(3,4),
Q(4,6),
R(4,5) d b.
Low Setpoint S
R(4)
S/U(1)
N.A.
N.A.
1,2 3.
Power Range, Neutron Flux, N.A.
R(4)
Q(17)
N.A.
N.A.
1, 2 High Positive Rate w
E (NI-0041B&C,NI-0042B&C, NI-0043B&C,NI-0044B&C) 4.
Deleted d
5.
Intermediate Range, S
R(4,5)
S/U(1)
N.A.
N.A.
I,2 Neutron Flux 5M (NI-0035B,D&E, y$
NI-0036B,D&G) c EE 6.
Source Range, Neutron Flux 5
R(4,5)
S/U(1),Q(9,17)
N.A.
N.A.
2, 3, 4, 5 (NI-00318,0&E, zz PP NI-00328,0&G) 7.
Overtemperature M S
R Q(17)
N.A.
N.A.
1, 2 (TDI-0411C, TDI-0421C, EE TDI-0431C,TDI-0441C) 33 50 i
.